Text

Initial Exam 2012-301 Draft SRO Written Exam
	ML12270A395
Person / Time
Site:	Oconee
Issue date:	09/24/2012
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	Download: ML12270A395 (51)
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ILT41 ONS SRO NRC Examination QUESTION 76 76j APEOO8 AA2.30 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)

Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: (CFR: 43.5 /45.13)

Inadequate core cooling Given the following Unit I conditions:

Initial conditions:

Reactor tripped from 100% power due to a transient

PORV is failed OPEN

I RC-4 will not CLOSE

Multiple equipment failures have occurred Current conditions:

EOP ICC tab in progress

CETCs = 754°F increasing

The TSC concurs with starting RCP(s)

In accordance with the ICC tab:

1) (1) willbestarted.

2) If required, RCP starting interlocks (2) be bypassed to start the RCP(s).

Which ONE of the following completes the statements above?

A. 1.ONLYIRCP

2. will B. 1. ONLY I RCP

2. will NOT C. 1. 1 RCP/loop

2. will D. 1. 1 RCP/loop

2. will NOT Wednesday, April 11, 2012 Page 151 of 202

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ILT41 ONS SRO NRC Examination QUESTION 76 L 76 General Discussion Answer A Discussion Incorrect. First part is plausible because during HPI F/C on RCP is left operating to limit heat input to the RCS. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because during HPI F/C on RCP is left operating to limit heat input to the RCS. Second part is plausible because in other places in the EOP, below 700 degrees, RCP interlocks will not be bypassed.. Example: LOHT tab If there is no heat transfer and SCM> 0 degrees then 1 RCP is started but interlocks are not bypassed.

Answer C Discussion Correct. In accordance with EOP ICC tab steps 39 and 40, 1RCP/loop will be started and RCP starting interlocks will be bypassed as required.

Answer D Discussion Incorrect. First part is correct. Second part is plausible because in other places in the EOP, below 700 degrees, RCP interlocks will not be bypassed.. Example: LOHT tab If there is no heat transfer and SCM> 0 degrees then I RCP is started but interlocks are not bypassed.

Basis for meeting the KA Question requires knowledge of the ICC tab which was entered as a result of Pzr vapor space accident.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions, this question requires assessing plant conditions (RCS temp) and selecting a section of a procedure with which to proceed (starting RCPs). Also requires detailed knowledge of the content of the procedure specific to the section being performed (how many RCPs will be started and will interlocks be bypassed).

The question is not systems knowledge.

The question is not Immediate Operator Actions.

The question cannot be answered from knowledge of entry conditions.

This question requires more specific knowledge than knowledge of the major mitigation strategy of the procedure.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EAP-ICC R7 EOP ICC tab APEOO8 AA2.30 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)

Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: (CFR: 43.5 / 45.13)

Inadequate core cooling 401-9 Comments: RemarkslStatus Wednesday, April 11, 2012 Page 152 of 202

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ILT41 ONS SRO NRC Examination QUESTION 77 77 APEO15/017 AA2.09 Reactor Coolant Pump (RCP) Malfunctions Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): (CFR 43.5 / 45.13)

When to secure RCPs on high stator temperatures Given the following Unit I conditions:

Initial conditions:

Reactor power = 70%

Current conditions:

IAI RCP Motor Stator temperature = 302°F stable

IAI Seal Return Temperature = 205°F stable

1) The IAI RCP is required to be secured due to high (1) temperature in accordance with AP/16 (Abnormal RCP Operation).

2) After the RCP is secured, maximum reactor power is limited to prevent exceeding (2) limits in accordance with TS 3.4.4 (RCS Loops MODES I and 2) bases.

Which ONE of the following completes the statements above?

A. 1. Motor Stator

2. KW/foot B. I. Motor Stator

2. DNB C. I. Seal Return

2. KW/foot D. I. Seal Return

2. DNB Wednesday, April 11, 2012 Page 153 of 202

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ILT41 ONS SRO NRC Examination QUESTION 77 77]

General DISCUSSiOn Answer A Discussion Incorrect. First part is correct. Second part is plausible because limiting reactor power limits KW/ft.

Answer B Discussion Correct. Per AP/16 the RCP must be secured if stator temperature exceeds 195 degrees. JAW TS B3.4.4 DNB is the concern.

Answer C Discussion Incorrect. First part is plausible because if seal return temperature were> 260 degrees this would be correct. Second part is plausible because limiting reactor power limits KW/ft.

Answer D Discussion Incorrect. First part is plausible because if seal return temperature were > 260 degrees this would be correct. Second part is correct.

Basis for meeting the KA Question requires knowledge of when to secure a RCP on high stator temperature and interpret the consequences of securing the pump.

Basis for Hi Coq Basis for SRO only This question requires knowledge of the consequenses of securing the RCP and from the basis of TS 3.4.4 that is not systems knowledge.

It cannot be answered by knowing 1 hr or less TS/TRM Action It cannot be answered solely with above the line information.

It cannot be answered solely by knowing Safety Limits Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided ADM-TSS R5 TSB 3.4.4 AP/1 6 APEOI5/017 AA2.09 Reactor Coolant Pump (RCP) Malfunctions Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): (CFR 43.5 /45.13)

When to secure RCPs on high stator temperatures 401-9 Comments: Remarks/Status Wednesday, April 11, 2012 Page 154 of 202

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ILT41 ONS SRO NRC Examination QUEST.!ON 78 APEO25 2.1.20 Loss of Residual Heat Removal System (RHRS)

APE025 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10/43.5 / 45.12)

Given the following Unit 1 conditions:

Initial conditions:

Reactor in MODE 6

Fuel Transfer Canal full

SF-I and SF-2 are open Current conditions:

Fuel Transfer Canal level slowly decreasing

RBNS level increasing

AP/26 (Loss of Decay Heat Removal) in progress Which one of the following describes the action that would be performed FIRST, in accordance with AP/26, and why?

A. Secure ALL LPI Pumps to determine if leak is on discharge of LPI Pumps B. Secure ALL LPI Pumps in preparation for closing 1SF-I and ISF-2 C. Secure SF Cooling pump used for Refueling Cooling Mode to determine if leak is on discharge of SF Cooling Pump D. Secure SF Cooling pump used for Refueling Cooling Mode in preparation for closing 1SF-I and 1SF-2 Wednesday, April 11,2012 Page 155 of 202

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ILT41 ONS SRO NRC Examination QUESTION 78 General Discussion Answer A Discussion Correct. Once you make your way to the correct section of AP/26 it will direct securing all LPI pumps in an effort to determine the location and isolability of the leak. If securing the pumps do not change the leak rate then they will be restarted.

Answer B Discussion Incorrect. First part is correct. Second part is plausible since the current SFC alignment in the refueling mode provides for taking a suction off the fuel transfer canal via the decay heat drop line and discharging to the SFP. That alignment must be secured prior to closing SF-l and 2 to prevent pumping FTC to SFP however it is the B SF pump being used in this alignment and not the LPI pumps.

Answer C Discussion Incorrect. Plausible since the B SFC Pump is being used in the Refueling Mode alignment and securing the pump and monitoring leak iate could help determine if the source of the leak is on the discharge of SFC pump. Since the Fuel Transfer Canal is full, securing the pump is plausible.

Additionally, this action is actually directed by AP/26 although it is a later action after transferring to the condition specific section of the AP. It is the LPI pumps that are initially secured.

Answer D Discussion rrect. Plausible since the SFC pumps are secured later in AP/26 prior to closing SF-I and 2 to prevent pumping FTC to SFP.

Basis for meeting the KA Requires knowledge of actions taken in AP/26 based on a decreasing fuel transfer canal and the ability to interpret the results of those actions to deterntine location and isolability of Fuel Transfer Canal leak.

Basis for Hi Cog Basis for SRO only In accordance with Rev. 1 of Clarification Guidance for SRO-only Questions:

This first part of this question requires detailed knowledge of specific procedure steps in AP/26. Knowledge of these steps are used to select which section of the procedure is to be performed. There are several sections of Subsequent Actions that could be performed based on the conditions requiring entry into the AP and using knowledge of the entry conditions and assessing the different sections of Subsequent actions is

[required to determine the appropriate steps to perform. Additionally, this question requires detailed knowledge of specific steps that need to be taken prior to transfer to section 4D. In this specific case, the LPI pumps are secured to assess the impact on the decreasing fuel transfer canal level. In this situation it is after these steps are performed that you make the transfer to section 4D which will direct stopping the SF Pump. This path through the AP means that to get to the appropriate actions you must assess plant conditions and determine a section of the procedure with which to proceed.

This question cannot be answered bases solely on systems knowledge since when in MODE 6 with fuel transfer canal full it would be normal to have LPI pumps running AND the B Spent Fuel Cooling pump aligned in the Refueling Cooling mode. Also, neither reason given for securing pumps would eliminate either answer based on system knowledge.

This question cannot be answered bases solely on knowledge of entry conditions.

None of the operator actions are Immediate Operator Actions of the AP.

The knowledge needed is more detail than just the major mitigation strategy of the AP.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ONS 2009B Q78 Development References APEO25 2.1.20 Loss of Residual Heat Removal System (RHRS)

APEO25 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 /45.12) 401-9 Comments: RemarkslStatus Wednesday, April 11, 2012 Page 156 of 202

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ILT41 ONS SRO NRC Examination QUESTION 79 79 APEO54 2.1.7 Loss of Main Feedwater (MFW)

APEO54 GENERIC Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 /45.12 / 45.13)

Given the following Unit I conditions:

Time = 0400

Reactor power = 100%

Time = 0405

Loss of ALL Main and Emergency Feedwater

RCS temperature is increasing

LOHT tab in progress Time = 0425

Core SCM = 0°F due to the RCS heatup The CRSRO will (1) and will direct (2)

Which ONE of the following completes the statement above?

A. 1. transfer to the LOS CM tab

2. initiating Rule 2 (Loss of SCM)

B. 1. transfer to the LOS CM tab

2. initiating full depressurization of both SGs C. 1. remain in the LOHT tab

2. initiating Rule 4 (Initiation of HPI Forced Cooling)

D. 1. remain in the LOHTtab

2. an operator to perform End 5.34 (Aligning SSF-ASW for SG Feed)

Wednesday, April 11, 2012 Page 158 of 202

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ILT41 ONS SRO NRC Examination QUEST..iON 79 79 General Discussion Answer A Discussion Incorrect. First part is plausible because if the loss of SCM was not due to heating up this would be correct. Second part is plausible because Rule 2 would still be initiated in this case.

Answer B Discussion Incorrect. First part is plausible because if the loss of SCM was not due to heating up this would be correct. Second part is plausible because this would be performed if HPI was degraded.

Answer C Discussion Correct. Per a note in the LOHT tab Transfer to LOSCM tab is NOT required if RCS heats to the point where core SCM = 0°F.. Per the LOHT tab if the RCS heats up to the point where core SCM = 0 degrees then Rule 4 will be initiated.

Answer D Discussion Incorrect. First part is correct. Second part is plausible because this would be done if HPI F/C was not adequate.

Basis for meeting the KA Question requires making operational judgments based on plant conditions caused by a loss of Main FDW. In this case selecting the correct procedure to mitigate the event.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions, this question requires assessing plant conditions and selecting a procedure with which to proceed to mitigate the event.

It cannot be answered by just knowing entry conditions. It requires detailed knowledge of the content of the procedure to make the correct choice to stay or transfer to another EOP tab.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided LOHT tab LOSCM tab APEO54 2.1.7 Loss of Main Feedwater (MFW)

APEO54 GENERIC Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13) 401-9 Comments: Remarks/Status Wednesday, April 11, 2012 Page 159 of 202

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ILT41 ONS SRO NRC Examination QUESTION 80 APEO58 2.2.38 Loss of DC Power APEO58 GENERIC Knowledge of conditions and limitations in the facility license. (CFR: 41.7 / 41.10 / 43.1 / 45.13)

Given the following plant conditions:

Initial conditions:

Date 4/5

All three Oconee Units at 100% power

Time=1100

3KVIB panelboard de-energized Current conditions:

Time1200

DC panelboard 3DIC is de-energized

1) Tech Spec LCO 3.8.8 (Distribution Systems-Operating) is NOT met for (1)

2) The bases behind the different Completion Times for inoperable Vital Instrument and Control panelboards (2)

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. Unit3 ONLY

2. KVIA AND KVIB have shorter completion times due to being the source of power for the ES Voters B. 1. Unit3 ONLY

2. KVIA AND KVIB have shorter completion times due to providing power for 5K and SL breakers protective relaying C. 1. Units 1,2, AND3

2. KVIA AND KVIB have shorter completion times due to being the source of power for the ES Voters D. 1. Units 1,2, AND3

2. KVIA AND KVIB have shorter completion times due to providing power for SK and SL breakers protective relaying Wednesday, April 11, 2012 Page 160 of 202

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ILT41 ONS SRO NRC Examination QUESTION 80 80 General Discussion Answer A Discusson Correct. 3DIC OOS will result in entering TS 3.8.8 Conditions C. KVIA and KVIB have shorter completion times due to powering the ES Voters.

Answer B Discussion Incorrect: : First part is Correct. Second part is plausible since SK and SL breakers protective relaying is singled out in the electrical specs as unique. It is unique because unit ls DIC and DID panelboards provide power to these breakers that all 3 units rely on. The fact that the power for SK and SL breakers comes from a units power panelboards and is singled out as unique in the electrical specs combine to make this a plausible distractor since Condition F is itself unique for other reasons. Additionally, the breakers are getting power from the c and d strings of panelboards however it is from the DC panelboards instead of the AC panelboards.

Answer C Discussion Incorrect. First part is plausible because it would be correct if it were IDIC. Second aprt is correct.

Answer D Discussion --__________

Incorrect. First part is plausible because it would be correct if it were 1DIC. Second part is plausible since SK and SL breakers protective relaying is singled out in the electrical specs as unique. It is unique because unit 1 s DIC and DID panelboards provide power to these breakers that all 3 units rely on. The fact that the power for SK and SL breakeis comes from a units power panelboards and is singled out as unique in the electrical specs combine to make this a plausible distractor since Condition F is itself unique for other reasons. Additionally, the breakers are getting power from the c and d strings of panelboards however it is from the DC panelboards instead of the AC panelboards.

Basis for meeting the KA Requires tracking previously entered TS LCOs and then correctly applying that to a subsequent inoperability to determine the correct actions required by Tech Specs.

Basis for Hi Cog Basis for SRO only Requires applying the generic LCO 3.0.3 rule to a situation where there are insufficient TS Conditions to cover all inoperabilitys that exist. This requirement is unique to the SRO position Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ONS 2009A SRO Q#80 Development References Student References Provided TS 3.8.8 and bases, TS 3.8.8 EL-DCD APEO58 2.2.3 8 Loss of DC Power APEO58 GENERIC Knowledge of conditions and limitations in the facility license. (CFR: 41.7 /41.10 / 43.1 / 45.13) 4O19 Comments: Remarks/Status Wednesday, April 11, 2012 Page 161 of 202

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ILT41 ONS SRO NRC Examination QUESTION 81 BWEO4 EA2. I Inadequate Heat Transfer Ability to determine and interpret the following as they apply to the (Inadequate Heat Transfer)

(CFR: 43.5 /45.13)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Given the following Unit I conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

ALL CBPs, Main and Emergency FDW pumps have tripped

2SA-1 8/A-I I (TURBINE BSMT WATER LEVEL EMERGENCY HIGH) actuated

The SRO has completed verification of IMAs

1) The SRO will transfer to the (1) tab of the EOP.

2) The next method that will be used to remove decay heat is (2) in accordance with the procedure identified above.

Which ONE of the following completes the statements above?

A. 1. TBF

2. feeding with the SSF ASW pump B. 1. TBF

2. initiation of HPI Forced Cooling C. 1. LOHT

2. feeding with the SSF ASW pump D. 1. LOHT

2. initiation of HPI Forced Cooling Wednesday, April 11, 2012 Page 162 of 202

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ILT41 ONS SRO NRC Examination QUESTION 81 General Discussion Answer A Discussion Incorrect. First part is plausible because although the entry conditions are met to transfer to the TBF tab, LOHT is a higher priority. Second part is plausible because in the TBF tab feeding with the SSF ASW pump would be the next method. Also if HPI F/C is not successful then feeding with the SSF ASW pump would be performed.

Answer B Discussion Incorrect. First part is plausible because although the entry conditions are met to transfer to the TBF tab, LOHT is a higher priority. Second part is plausible because in the TBF tab feeding with the SSF ASW pump would be the next method. Also if HPI F/C is not successful then feeding with the SSF ASW pump would be performed.

Answer C Discussion Incorrect. First part is correct. Second part is plausible because in the TBF tab feeding with the SSF ASW pump would be the next method.

Also if HPI F/C is not successful then feeding with the SSF ASW pump would be performed.

Answer D Discussion Correct. LOHT is the highest priority tab that applies at this time. In the LOHT tab HPI F/C is the next method to remove decay heat.

Basis for meeting the KA The question requires the candidate to evaluate plant conditions and determine that a LOHT conditions and a TBF exist and then pick the appropriate procedure to use to mitigate the event.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1 this question is at the SRO level as described below:

The question requires Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. The entry conditions for two EOP tabs exist. It is SRO knowledge to determine the highest priority tab.

The question cannot be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location.

The question cannot be answered solely by knowing immediate operator actions.

The question cannot be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs.

The question cannot be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure?

Job Level Cognitive Level QuestionTypo Question Source SRO Comprehension NEW Development References Student References Provided EOP SA EOP LOHT Tab EOP TBF Tab BWEO4 EA2.l Inadequate Heat Transfer Ability to determine and interpret the following as they apply to the (Inadequate Heat Transfer)

(CFR: 43.5 / 45.13)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

401-9 Comments: arks!Status Wednesday, April 11, 2012 Page 163 of 202

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ILT41 ONS SRO NRC Examination QUESTION 82 82 APE036 2.1.32 Fuel Handling Incidents APEO36 GENERIC Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2/45.12)

Given the following Unit I conditions:

Initial conditions:

Re-fueling in progress Current conditions:

A fuel assembly is damaged while inserting into the core

An adjacent assembly must be placed in an alternate core location while recovering the damaged assembly Which ONE of the following states the MINIMUM level of approval required to place a fuel assembly into an alternate location other than the original one assigned by the Core Reload Sequence in accordance with MPIOIAJI 500/009 (Defueling/Refueling Procedure) Limits and Precautions?

A. Refueling SRO Assistant B. Reactor Building SRO C. Refueling SRO D. OSM Wednesday, April 11, 2012 Page 165 of 202

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ILT41 ONS SRO NRC Examination QUESTION 82 82 General Discussion Answer A Discussion Incorrect. Plausible since this position is involved in the step by step implementation of the refueling procedures and this position is the one required to administratively verify that the assembly is being inserted into the position required by the procedure.

Answer B Discussion Incorrect. Plausible since this is an SRO position required to be inside the Rx Bldg during core alterations and it is a position required to be staffed by SLC 16.13.1 (Minimum Station Staffing Requirements). Additionally plausible since this position is responsible for the overall conduct of fuel handling operations in the Reactor Building.

Answer C Discussion Correct. In accordance with the procedures use to control fuel handling activities:

During refueling, IF Any Fuel Assembly must be placed in a Core location other than the one assigned in PT/0/A10750/0 18, Refueling Activities, then the alternate core location shall be evaluated by a Qualified Reactor Engineer and approved by the Refueling SRO.

Answer D Discussion Incorrect. Plausible since in general the OSM is required to approve deviations from procedures. However, this specific case has rmre specific requirements in the procedure being used to perform the fuel movement.

Basis for meeting the KA Question requires knowledge of Fuel Handling Limits and Precautions concerning bypassing Fuel Handling Bridge interlocks.

Basis for Hi Cog Basis for SRO only In accordance with Rev. I ofClarification Guidance for SRO-only Questions:

This question requires knowledge of fuel handling procedures and knowledge of the requirements necessary to change/deviate from a plant procedure.

Additionally, this requires knowledge of an activity that is defined as an SRO only activity in plant procedures.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ONS 2009B Q9l Development References Student References Provided FH-FHS R27 Refueling Procedure (MP/0/l 500/009)

APEO36 2.1.32 Fuel Handling Incidents APE036 GENERIC Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 401-9 Comments: Remarks/Status Wednesday, April 11, 2012 Page 166 of 202

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ILT41 ONS SRO NRC Examination QUESTION 83 83]

APEO28 AA2.1O Pressurizer (PZR) Level Control Malfunction Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfl.inctions: (CFR: 43.5 /45.13)

Whether the automatic mode for PZR level control is functioning improperly, necessity of shift to manual modes Given the following Unit I conditions:

Initial conditions:

Reactor power = 100%

Pressurizer (PZR) Level 2 selected

SASS in MANUAL Current conditions:

ICCM Train lA experiences a total loss of power

1) 1 HP-120 (1) required to be taken to MANUAL to prevent exceeding the Pzr level limit in TS 3.4.9 (Pressurizer).

2) The bases for the limit on Pzr level in TS 3.4.9 (Pressurizer) is to (2)

Which ONE of the following completes the statements above?

A. 1.is

2. prevent exceeding the RCS pressure Safety Limit due to a subsequent Pzr i nsurge B. 1.is

2. ensure that a RCP start at power would not cause a pressure spike which would approach the RCS pressure Safety Limit C. 1. is NOT

2. prevent exceeding the RCS pressure Safety Limit due to a subsequent Pzr insurge D. 1. is NOT

2. ensure that a RCP start at power would not cause a pressure spike which would approach the RCS pressure Safety Limit Wednesday, April 11, 2012 Page 167 of 202

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ILT41 ONS SRO NRC Examination QUESTION 83 General Discussion Answer A Discussion Correct. ICCM Train A feeds Pzr level I and 2. A loss of power to 1A ICCM Train will cause Pzr Level 2 to fail low and cause 1HP-120 to fully open. The operator must take manual control of 1HP-120 to prevent the Pzr from exceeding the TS limit on level. TSB 3.4.9 states: If the level limits were exceeded prior to a transient that creates a large pressurizer insurge volume, the maximum RCS pressure could exceed the design Safety Limit (SL) of 2750 psig.

Answer B Discussion Incorrect. First part is correct. Second part is plausible because there am Pzr level limits associated with starting a RCP and misconception could be that the level limit was based on causing a pressure spike..

Answer C Discussion Incorrect. Plausible because the candidate could have the misconception that Pzr level 2 was fed from ICCM Train lB. Second part is correct.

Answer D Discussion tncorrect. Plausible because the candidate could have the misconception that Pzr level 2 was fed from ICCM Train lB. Second part is plausible because there are Pzr level limits associated with starting a RCP and misconception could be that the level limit was based on causing a pressure spike..

Basis for meeting the KA Question requires the candidate to determine if I HP-I 20 is required to be placed in manual for a given situation Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions:

This question requires knowledge from the basis of TS 3.4.9 that is not systems knowledge.

It cannot be answered by knowing 1 hr or less TS/TRM Action It cannot be answered solely with above the line information.

It cannot be answered solely by knowing Safety Limits Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided PNS-PZR R35 TS B3.4.9 APEO28 AA2.I0 Pressurizer (PZR) Level Control Malfunction Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: (CFR: 43.5 / 45.13)

Whether the automatic mode for PZR level control is functioning improperly, necessity of shift to manual modes ji-s Comments: Remarks/Status Wednesday, April 11, 2012 Page 168 of 202

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ILT41 ONS SRO NRC Examination QIJESI.ION 84 84 BWEO3 EA2.2 Inadequate Subcooling Margin Ability to determine and interpret the following as they apply to the (Inadequate Subcooling Margin)

(CFR: 43.5 /45.13)

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

lCHPlpumpOOS

SBLOCA occurs Current conditions:

ALL SCMs = 0

I B HPI pump tripped and will NOT start

1) The LOSCM tab will give direction to depressurize BOTH SGs (1)

2) 1 OCFR5O.46 ECCS acceptance criteria (2) be met.

Which ONE of the following completes the statements above?

A. 1. fully

2. will B. 1. fully

2. will NOT C. 1. to 250 psig

2. will D. 1. to 250 psig

2. will NOT Wednesday, April 11,2012 Page 169 of 202

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ILT41 ONS SRO NRC Examination QUESTION 84 L 84 General Discussion Answer A Discussion Incorrect. First part is correct. Second part is plausible because it would be correct if power were below 75% when the event occurs.

Answer B Discussion Correct. The LOSCM tab will direct depressurizing both SG because HPI (only one HPI pump is operating) is degraded. Per TS 3.5.2 bases the ECCS acceptance criteria will not be met with just one train of HPI because power is above 75% when the event occurred.

Answer C Discussion

[icorrect. First part is plausible because it would be correct if only the TDEFDW pump was operating. Second part is plausible because it be correct if power were below 75% when the event occurs.

Answer D Discussion Incorrect. First part is plausible because it would be correct if only the TDEFDW pump was operating. Second part is correct.

Basis for meeting the KA Question requires knowledge of how to comply with the appropriate facility procedures during a loss of SCM.

Basis for Hi Cog Basis for SRO only This question requires knowledge from the basis of TS 3.5.2 (HPI) that is not systems knowledge.

It cannot be answered by knowing 1 hr or less TS/TRM Action It cannot be answered solely with above the line information.

It cannot be answered solely by knowing Safety Limits Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided LOSCM tab TS B3.5.2 BWEO3 EA2.2 Inadequate Subcooling Margin Ability to determine and interpret the following as they apply to the (Inadequate Subcooling Margin)

(CFR: 43.5 /45.13)

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

401-9 Comments: Remarks/Status Wednesday, April 11, 2012 Page 170 of 202

FOR REVIEW ON*Y DO NOT DISTRIBUTE ILT41 ONS SRO NRC Examination QUESTION 85 85 BWEI4 2.4.20 EOP Enclosures BWEI4 GENERIC Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 /43.5 / 45.13)

Given the following Unit I conditions:

SSF has been activated

EOP Enclosure 5.34 (Aligning SSF-ASW for SG Feed) in progress

1) In accordance with a NOTE in Enclosure 5.34, the alignment of SSF Diesel Service Water discharge to the yard drain must be completed (1) of the SSF Diesel emergency start.

2) A reason for the above action is to ensure continued operability of the SSF (2)

Which ONE of the following completes the statements above?

A. 1. between I hourand45 minutes and 2hours

2. HVAC system B. 1. between 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 45 minutes and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

2. ASW pump C. I. within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 20 minutes

2. HVAC system D. I. within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 20 minutes

2. ASW pump Wednesday, April 11, 2012 Page 171 of 202

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ILT41 ONS SRO NRC Examination QUESTION 85 L General Discussion Answer A Discussion Correct. The SSF Diesel Service Water discharge must be diverted to the yard drain between 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 45 minutes and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . This is done in part to ensure SSF HVAC operability.

Answer B Discussion Incorrect: First part is correct. Second part is plausible since the ASW pump also takes a suction on the CCW crossover piping.

Answer C Discussion Incorrect. First part is plasuible because 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 20 minutes the allowed time to Submersible pump in place after the SSF Diesel is emergerncy started. Second part is correct.

Answer D Discussion Incorrect. First part is plasuible because 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 20 minutes the allowed time to Submersible pump in place after the SSF Diesel is emergemcy started. Second part is plausible since the ASW pump also takes a suction on the CCW crossover piping.

Basis for meeting the KA Question requires knowledge of the operational implications of a NOTE in an EOP enclosure.

Basis for Hi Cog Basis for SRO only

[This question requires detailed knowledge of a NOTE in an EOP enclousre and the bases for the action taken.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EAP-SSF EOP End. 5.34 BWEI4 2.4.20 EOP Enclosures BWE1 4 GENERIC Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10/ 43.5 /45.13) 401-9 Comments: RemarkslStatus Wednesday, April 11,2012 Page 172 of 202

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ILT41 ONS SRO NRC Examination QUESTION 86 SYSOO6 2.4.40 Emergency Core Cooling System (ECCS)

SYS0O6 GENERIC Knowledge of SRO responsibilities in emergency plan implementation.

Given the following Unit 2 conditions:

Time = 0900

Reactor power = 100%

Time = 0904

ES Channels I & 2 actuated on low RCS Pressure

The 2B and 2C HPI pumps failed to Auto start and cannot be started manually Time = 0910

ALL SCMs = 0°F stable

RCS pressure = 1000 psig stable

RB Pressure = 7 psig increasing

2RIA-57 = 200 R/HR increasing Time 0912

2RIA-57 = 350 R/HR stable

RB Pressure = 1 psig rapidly decreasing Without using the Emergency Coordinator Judgment option, which ONE of the following:

1) states the EAL classification required by the conditions at 0910?

2) states the EAL classification required by the conditions at 0912?

REFERENCE PROVIDED A. 1. Alert

2. Site Area Emergency B. 1. Alert

2. General Emergency C. 1. Site Area Emergency

2. Site Area Emergency D. 1. Site Area Emergency

2. General Emergency Wednesday, April 11, 2012 Page 173 of 202

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ILT41 ONS SRO NRC Examination QUESTION 86 86j General Discussion Answer A Discussion orrect. First part is correct. Second part is plausible if the candidate does not realize that containment has been breached.

Answer B Discussion Correct. First part is correct. At 0910 is an Alert based on 5 points for RCS Leak rate that results in a loss of subcooling. Second part is correct. At 0920 a General Emergency is declared based on:

RCS Barrier 5 points - Loss of subcooing or 2RIA-57> 1.6 RJhr Fuel Clad Barrier - 5 points RIA-57 -> 300 R!hr < 30 minutes Containment Barrier 3 points Containment isolation is incomplete...

Total points = 13 (General Emergency)

Answer C Discussion Incorrect. First part is plausible because the candidate may add 4 points for RCS leak> 160 and Loss of SCM for a total of 9 points. This would be a SAE. Second part is plausible if they miss the containment breach.

Answer D Discussion Incorrect. First part is plausible because the candidate may add 4 points for RCS leak> 160 and Loss of SCM for a total of 9 points. This would be a SAE. Second part is correct.

Basis for meeting the KA Question requires knowledge of E Plan classification with a failure of ECCS components. This failure results in a loss of SCM. This is an SRO responsibility involving the Eplan.

Basis for Hi Cog Basis for SRO only This questions requires EAL determinations which are activities performed only by SROs and have SRO specific objectives.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided RP/l 000/001 RP/l 000/00 1 SYSOO6 2.4.40 Emergency Core Cooling System (ECCS)

SYSOO6 GENERIC Knowledge of SRO responsibilities in emergency plan implementation.

401-9 Comments; Remarks/Status Wednesday, April 11, 2012 Page 174 of 202

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ILT41 ONS SRO NRC Examination QUESTION 87 87!

SYSOO7 A2.O1 Pressurizer Relief Tank/Quench Tank System (PRTS)

Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5/45.3 / 45.13)

Stuck-open PORV or code safety Given the following Unit I conditions:

Time = 0400

Reactor power = 100%

BOTH Main FDWpumpstrip Time = 0403

Reactor power = 68% decreasing

RULE I (ATWS/UNPP) is complete

I RC-66 is failed open

RCS pressure = 1920 psig decreasing Time = 0410

Reactor power 5% decreasing

UNPP tab in progress

QT pressure = 12 psig increasing

1) The MINIMUM QT pressure which will result in reactor coolant being released to the RB atmosphere is (1) psig.

2) If 1 RC-4 will NOT close, the (2) tab will be used to mitigate this event and place LPI in service.

Which ONE of the following completes the statements above?

A. 1.49

2. HPICD B. 1.49

2. LOCACD C. 1.55

2. HPICD D. 1.55

2. LOCACD Wednesday, April 11,2012 Page 175 of 202

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ILT41 ONS SRO NRC Examination QUES1[1.ON 87 L 87 General Discussion Answer A Discussion Incorrect. First part is plausible because 49 psig is the highest pressure allowed in the QT per L&P of the QT operating procedure. Second part is plausible because the plant condition are very similar to being in HPI forced cooling. i.e. HPI pumps are operating and there is flow through the PORV. If in HPI forced cooling then transfer to HPI CD would be correct.

Answer B Discussion Incorrect. First part is plausible because 49 psig is the highest pressure allowed in the QT per L&P of the QT operating procedure. Second part is correct.

Answer C Discussion Incorrect. First part is correct. Second part is plausible because the plant condition are very similar to being in HPI forced cooling. i.e. HPI pumps are operating and there is flow through the PORV. If in HPI forced cooling then transfer to HPI CD would be correct.

Answer D Discussion Correct. The QT rupture disk ruptures at 55 psig in the QT. Transfer to the LOCA CD tab will be made either from Subsequent Actions or if SCM is lost from LOS CM tab.

Basis for meeting the KA Question requires knowledge of the impacts to the QT of the PORV being open and what EOP enclosure will give guidance on how to shut down to LPI.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions, this question requires assessing plant conditions and selecting a procedure with which to proceed to mitigate the event.

It cannot be answered by just knowing entry conditions. It requires detailed knowledge of the content of the procedure to make the correct choice.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided PNS-CS R7 OP/i 104/017, QT Operation EOPIMAs LOSCM tab SYSOO7 A2.0l Pressurizer Relief Tank/Quench Tank System (PRTS)

Ability to (a) predict the impacts of the following malfunctions or operations on the P 5; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

Stuck-open PORV or code safety 401-9 Comments: RemarkslStatus Wednesday, April 11,2012 Page 176 of 202

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ILT41 ONS SRO NRC Examination QIJESTION 88 88 SYSO6I A2.08 Auxiliary / Emergency Feedwater (AFW) System Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 /45.3 / 45.13)

Flow rates expected from various combinations of AFW pump discharge valves Given the following Unit I conditions:

Initial conditions:

Reactor power =100%

BOTH Main FDW pumps trip Current conditions:

ALL EFDW pumps operating

MDEFDWP DICH FLOW LOOP A = 100 gpm

MDEFDWP DICH FLOW LOOP B = 150 gpm

TOTAL EFDW FLOW IA = 100 gpm

TOTAL EFDW FLOW I B = 275 gpm

1) The cause of these indications is (1)

2) In accordance with TS 3.7.5, a MAXIMUM of (2) is allowed to open the mis-positioned valve.

Which ONE of the following completes the statements above?

A. 1. 1 FDW-368 (TDEFDWP DISCH TO IA SG BLK) is CLOSED

2. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. 1. 1 FDW-368 (TDEFDWP DISCH TO IA SG BLK) is CLOSED

2. 7 days C. 1. 1 FDW-374 (1A MD EFDWP DISCHARGE to S/G A) is CLOSED

2. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D. 1. 1 FDW-374 (IA MD EFDWP DISCHARGE to S/G A) is CLOSED

2. 7 days Wednesday, April 11, 2012 Page 177 of 202

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ILT41 ONS SRO NRC Examination QUESTION 88 [

General Discussion Answer A Discussion Correct. 1FDW-368 being closed will give these indications. IFDW-368 being closed makes the TDEFDWP inoperable. TS 3.7.5 Condition B would be entered with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Answer B Discussion Incorrect. First part is correct. Second part is plausible because it would be correct if a MDEFDW pump were inoperable.

Answer C Discussion Incorrect. First part is plausible because the candidate could have the misconception that 1FDW-374 is the lA MDEFDWP dischagre valve and that it is down stream of the line from the TD EFDWP. Second part is correct.

Answer D Discussion Incorrect. First part is plausible because the candidate could have the misconception that IFDW-374 is the IA MDEFDWP dischagre valve and that it is down stream of the line from the TD EFDWP. Second part is plausible because it would be correct if a MDEFDW pump were noperable.

Basis for meeting the KA Question requires evaluating plant data and determining which valve is misaligned and based on this information determine whether the affe DWP is operable. This inoperability would then lead to the taking the TS required action to correct the situation.

Basis for Hi Cog Basis for SRO only This question requires knowledge of TS 3.7.5 that is not systems knowledge.

It cannot be answered by knowing 1 hr or less TS/TRM Action It cannot be answered solely with above the line information.

It cannot be answered solely by knowing Safety Limits Job Level SRO Cognitive Level Comprehension

[ QuestionType NEW Question Source Development References Student References Provided ADM-TSS R5 EFDW Drawing TS3.7.5 SYSO6I A2.08 Auxiliary! Emergency Feedwater (AFW) System Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 /45.3 / 45.13)

Flow rates expected from various combinations of AFW pump discharge valves i19 Comments: Remarks/Status I

Wednesday, April 11,2012 Page 178 of 202

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ILT41 ONS SRO NRC Examination QUESTION 89 89 SYSO63 2.4.12 DC Electrical Distribution System SYS063 GENERIC Knowledge of general operating crew responsibilities during emergency I operations. (CFR: 41.10 / 45A 2)

Given the following Unit I conditions:

Time = 0400:

Station blackout in progress Time = 0405

OSM determines I DCA (Control Battery Bus) is de-energized

OSM and the STA discuss the I DCA issue and develop a plan to restore it Time = 0410

Power restored to both Main Feeder Buses form KHU #1 and CT-I

CT-5isenergized Time = 0430

IDCA energized I) In accordance with OMP 1-18 (Implementation Standard During Abnormal and Emergency Events), the (I) will conduct the Focus Brief on restoration of the battery charger.

2) In accordance with RP/0/B/1000/001 (Emergency Classification) the highest emergency classification (if any) for the above sequence of events is (2)

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. OSM ONLY

2. none B. I. OSM ONLY

2. Site Area Emergency C. I. OSMortheCRSRO

2. none D. I. OSMortheCRSRO

2. Site Area Emergency Wednesday, April 11,2012 Page 179 of 202

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ILT41 ONS SRO NRC Examination QUESTION 89 89 General Discussion Answer A Discussion

[Iorrect. First part is plausible because the OSM normally would conduct the Focus Brief. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because the OSM normally would conduct the Focus Brief. Second part is plausible because it would be correct if both DC buses were dc-energized greater than 15 minutes.

Answer C Discussion Correct. Per OMP 1-18, the OSM is responsible for the focused brief. However if the OSM is not available the CRSRO (PD) is allowed to conduct the brief. With only one DC bus dc-energized for greater than 15 minutes then this event does not meet a classification threshold.

Answer 0 Discussion

[iorrect. First part is correct. Second part is plausible because it would be correct if both DC buses were dc-energized greater than 15 minutes.

Basis for meeting the KA Question requires knowledge of the OSM and the CRSRO responsibilities during an emergency involving a part of the DC system.

Basis for Hi Cog Basis for SRO only

[estion requires knowledege of OSM resonsibilities during an emergemcy including emergency plan classification.

Job Level Cognitive Lev& QuestionType Question Source SRO Comprehension NEW Development References Student References Provided ADM-OMP P..PJo/B/l 000/001 OMP 1-18 RP/0!B/1000/001 SYSO63 2.4.12 DC Electrical Distribution System SYSO63 GENERIC Knowledge of general operating crew responsibilities during emergency I operations. (CFR: 41.10 / 45.12) 401-9 Comments: Remarks/Status Wednesday, April 11,2012 Page 180 of 202

FOR REVIEW ONLY DO NOT DISTRIBUTE ILT41 ONS SRO NRC Examination QUESTION 90 9O SYSO64 2.2.22 Emergency Diesel Generator (ED/G) System SYSO64 GENERIC Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2)

Given the following Unit I conditions:

Initial conditions:

Reactor power = 100%

ACB-3 closed Which ONE of the following will make the overhead emergency power path inoperable in accordance with TS 3.8.1 (AC Sources Operating) Bases?

A. ACB-2 inoperable B. Zone overlap interlock inoperable C. ACB-1 to ACB-3 interlock inoperable D. One channel of Switchyard Isolation inoperable Wednesday, April 11, 2012 Page 181 of 202

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ILT41 ONS SRO NRC Examination QUESTION 90 General Discussion Answer A Discussion Correct. Per the table in TS B3.8.l if ACB-3 is closed it designates KHU #1 as the underground unit. If KHU #1 is the underground unit then if ACB-2 is inoperable it will make the overhead power path inoperable.

Answer B Discussion Incorrect. Plausible because Zone Overlap is an LCO for TS 3.8.1 but does not make the overhead power path inoperable.

Answer C Discussion

[irect. Plausible because it would be correct if ACB-4 were closed.

Answer D Discussion irrect. Plausible because it would be correct if both channels were inoperable Basis for meeting the KA Requires adherence the Tech Specs in support of limiting conditions for operation. The overhead path is one of two ways the Keowee units get power to the nuclear units.

Basis for Hi Cog Basis for SRO only This question requires knowledge from the basis of TS 3.8.1 that is not systems knowledge.

It cannot be answered by knowing 1 hr or less TS/TRM Action It cannot be answered solely with above the line information.

It cannot be answered solely by knowing Safety Limits Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided TSB3.8.1 TS 3.8.1 SYSO64 2.2.22 Emergency Diesel Generator (ED/G) System SYSO64 GENERIC Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2) 401-9 Comments: RemarkslStatus Wednesday, April 11,2012 Page 182 of 202

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ILT41 ONS SRO NRC Examination QUESTION 91 SYSO16 A2.02 Non-Nuclear Instrumentation System (NNIS)

Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)

Loss of power supply Given the following Unit I conditions:

Initial conditions:

Time 0400

Reactor power 100%

Current conditions:

Time=0415

HPI X-OVER LOOP A flow instrument loses power

1) If at 0400, ES Channels I 8 actuated the HPI X-OVER LOOP A flow instrument (1) indicate flow.

2) At 0415, TS 3.5.2 (HPI) CONDITION A (2) required to be entered.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. would

2. is B. 1. would

2. is NOT C. 1. would NOT

2. is D. 1. would NOT

2. is NOT Wednesday, April 11,2012 Page 183 of 202

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ILT41 ONS SRO NRC Examination QUESTION 91 9l General Discussion Answer A Discussion Incorrect. First part is plausible because the candidate could have the misconception that the X-over flow instrument was in the normal flow path. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because the candidate could have the misconception that the X-over flow instrument was in the normal flow path. Second part is plausible because the candidate could have the misconception that the x-over flow instrument was not required for x-over valve operability.

Answer C Discussion Correct. During a ES actuation would out any failures, flow would not be indicated on the X-over instrument. Per TS 3.5.2 Bases the x-over flow instrument is required for the crossover valves to be operable. As a result Condition A will be entered.

Answer D Discussion Incorrect, First part is correct. Second part is plausible because the candidate could have the misconception that the x-over flow instrument was qired for x-over valve operability.

Basis for meeting the KA Question requires knowledge concerning the affect of a loss of NNI power to an HPI flow instrument and TS condition required to be entered as a result of the failure.

Basis for Hi Cog LBasis for SRO ony In accordance with Rev. I of Clarification Guidance for SRO-only Questions:

Requires knowledge from the Bases of TS 3.5.2 (HPI) regarding requirement of HPI X-over flow instrumentation on X-over valve operability and is not system knowledge information.

This question cannot be answered Solely on 1 hr or less TS knowledge.

This question cannot be answered based on above the line IS information.

This question cannot be answered with TS Safety Limit information.

Job Level Cognitive Level Questionlype Question Source SRO Comprehension NEW Dev&opment References Student References Provided TS 3.5.2 TS 3.5.2 TS B3.5.2 SYSO16 A2.02 Non-Nuclear Instrumentation System (NNIS)

Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 /45.5)

Loss of power supply 401-9 Comments: RemarkslStatus Wednesday, April 11,2012 Page 184 of 202

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ILT41 ONS SRO NRC Examination QUESTION 92 92!

SYSO34 2.1.35 Fuel Handling Equipment System (FHES)

SYSO34 GENERIC Knowledge of the fuel-handling responsibilities of SROs.

Given the following Unit I conditions:

Reactor in MODE 6

Refueling in progress

TS-3 (Bridge Bypass bridge left) requires bypassing In accordance with OP/01A115061001 (Fuel and Component Handling), which ONE of the following list contains the MINIMUM individual(s) who are required to authorize bypassing the above interlock?

A. Reactor Engineer ONLY B. Fuel Handling Supervisor ONLY C. Licensed Senior Reactor Operator AND Reactor Engineer D. Licensed Senior Reactor Operator AND Fuel Handling Supervisor Wednesday, April 11, 2012 Page 185 of 202

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ILT41 ONS SRO NRC Examination QUESTION 92 92 General Discussion Answer A Discussion Incorrect. Plausible because a Reactor Engineer is required to authorize bypassing some interlocks. However not this one.

Answer B Discussion Incorrect. Plausible because a Fuel Handling Supervisor is required to authorize bypassing this interlock but not the only one.

Answer C Discussion Incorrect. Plausible because a Reactor Engineer is required to authorize bypassing some interlocks. However not this one. The SRO approval is also required for bypassing this interlock.

Answer D Discussion Correct. Per OP/i 506/001 (End. 3.14) a Licensed SRO and the Fuel handling Supervisor are required to approve bypassing this interlock.

Basis for meeting the KA Question requires knowledge of a SRO fuel handling responsibility.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions:

Requires knowledge of SRO responsibilities during fuel handling operations.

Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided

SF-FHSR36 OP/i 506/001 SYSO34 2.1.35 Fuel Handling Equipment System (FHES)

SYSO34 GENERIC Knowledge of the fuel-handling responsibilities of SROs.

401-9 Comments: RemarkslStatus Wednesday, April 11, 2012 Page 186 of 202

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ILT41 ONS SRO NRC Examination QUESTION 93 93 SYSO68 2.2.40 Liquid Radwaste System (LRS)

SYSO68 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 / 45.3)

Given the following Unit I conditions:

Initial conditions:

Time=1200

1 RIA-54 removed from service for planned maintenance Current conditions:

Time=1235

1 RIA-54 returned to service Which ONE of the following states ALL SLC 16.11.3 (Radioactive Effluent Monitoring Instrumentation) conditions that apply (if any) at 1200?

REFERENCE PROVIDED A. None B. Band F ONLY C. BandHONLY D. B,F,andH Wednesday, April 11,2012 Page 187 of 202

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ILT41 ONS SRO NRC Examination QUESTION 93 93 General Discussion Answer A Discussion Incorrect. Plausible since there are several conditions in SLC 16.11.3 that provide for allowing a short < ihr planned outage of required RIAs or RIA components without having to enter the Condition for that RIA or component being inoperable. Therefore referring to the wrong condition or based on sight recognition of the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months controlled outage, attempting to answer without looking up the correct condtions could result in making this choice.

Answer B Discussion

[ect. RIA-54 being inoperable results in entry into Condition B. Required Action B.1 requires using Table 16.11.3-ito determine additional Conditions that apply. The table for RIA-54 refers to Condition F.

Answer C Discussion Incorrect. Condition B is correct. Condition H is plausible since it would be correct for the Sample Flow Monitor associated with RIA-54 being inoperable (per Table 16.11.3-1).

Answer D Discussion Incorrect. Conditions B and F are correct and Condition H is plausible since it would be correct for the Sample Flow Monitor associated with RIA-54 being inoperable (per Table 16.11.3-1).

Basis for meeting the KA Requires applying SLC 16.11.3 to the LWR system.

Basis for Hi Cog Requires application of a Tech Spec.

Basis for SRO only jicordance with Rev 1 guidance of Clarification Guidance for SRO-only Questions, this question requires application of a SLC to determine which Required Actions would apply. The question cannot be answered based on knowing 1 hr or less TS, above the line information, or Tech Spec Safety Limit information.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided ADM-ITS Obj. R6 L3 16.11.3 SLCI6.ll.3 SYSO68 2.2.40 Liquid Radwaste System (LRS)

SYSO68 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10 /43.2 / 43.5 / 45.3) 401-9 Comments: RemarkslStatus Wednesday, April 11, 2012 Page 188 of 202

FOR REVIEW ONLY DO NOT DISTRIBUTE ILT41 ONS SRO NRC Examination QUESTION 94 94 GEN2.1 2.1.43 GENERIC Conduct of Operations Conduct of Operations Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 / 45.6)

Given the following Unit 1 conditions:

An Estimated Critical Position (ECP) of Group 7 @ 30% withdrawn is calculated as follows:

400 EFPD

535 °F RCS Temperature

200 ppmB RCS boron concentration

(-1 .47%) Ak/k Xenon/Samarium Concentration

1) (1) will result in an ECP of CRD Group 7 greater than 30% withdrawn.

2) In accordance with the OP/1/A/1102/001 (Controlling Procedure for Unit Startup), if criticality is NOT achieved within +/- 0.75% Ak/k of the ECP then (2)

Which ONE of the following completes the statements above?

A. 1. 537° F RCS temperature

2. fully insert ALL safety and regulating rod groups B. 1. 537°F RCS temperature

2. insert ALL control rod groups to group 1 at 50% ONLY C. 1. 190 ppmB RCS boron concentration

2. fully insert ALL safety and regulating rod groups D. 1. 190 ppmB RCS boron concentration

2. insert ALL control rod groups to group 1 at 50% ONLY Wednesday, April 11, 2012 Page 189 of 202

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ILT41 ONS SRO NRC Examination QUESTION 94 [

94 General Discussion Answer A Discussion incorrect. First part is correct. Second part it is plausible to believe that a shutdown must be performed and inserting all control rods is required.

Answer B Discussion Correct. An increase in RCS temperature would add negative reactivity which would require Group 7 rods to be further withdrawn. Enclosure 4.7 of Op/i/A/i 102/001 step 3.21 requires that rods be inserted to Group 1 at 50% if criticality not achieved within .75%.

Answer C Discussion Incorrect. First part is plausible if Boron concentration increased it would be correct. Second part it is plausible to believe that a shutdown must be performed and inserting all control rods is required.

Answer D Discussion Incorrect. First part is plausible if Boron concentration increased it would be correct. Second part is correct.

Basis for meeting the KA Question requires knowledge of the affect of various plant parameters on reactivity and how this would affect the reactivity balance procedure..

Basis for Hi Cog Basis for SRO only This requires detailed knowledge of the Startup procdure and this procedure is always ran by the SRO.

Job Level Cognitive Level QuostionType Question Source SRO Comprehension MODWIED 2007 Retest Q#67 Development References . Student References Provided OP/I/A/l 102/001 GEN2. 1 2.1.43 GENERIC Conduct of Operations Conduct of Operations Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 / 45.6) 4019 Comments: Remarks/Status Wednesday, April 11, 2012 Page 190 of 202

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ILT41 ONS SRO NRC Examination QIJESI[1.ON 95 95 GEN2.2 2.2.15 GENERIC Equipment Control Equipment Control Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.10 / 43.3/45.13)

Given the following Unit I conditions:

Makeup to the 1&2 SEP from 2A BHUT is desired Per OMP 1-02 (Rules Of Practice):

1) the (I) is required to mark up the prints in the WCC and the Control Room.

2) this evolution (2) allowed to be controlled from WCC.

Which ONE of the following completes the statements above?

A. 1. responsible WCC SRO

2. is B. 1. responsible WCC SRO

2. is NOT C. 1. Control Room SRO

2. is D. 1. Control Room SRO

2. is NOT Wednesday, April 11,2012 Page 191 of 202

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ILT41 ONS SRO NRC Examination QUESTION 95 General Discussion Answer A Discussion 1

Incorrect. First part is plausible because the WCC SRO does mark up procedures and other documents that can affect the CR. Second part is plausible because WCC does control some evolutions that are approved by the CR. Such as tag outs.

Answer B Discussion Incorrect. First part is plausible because the WCC SRO does mark up procedures antd other documents that can affect the CR. Second part is correct.

Answer C Discussion Incorrect. First part is correct. Second part is plausible because other activities are approved by the CRSRO but controlled by the WCC. Tag outs would be an example.

Answer D Discussion Correct, The CRSRO is required to markup the drawing in both locations if it will be controlled from the CR. All water movement shall be controlled from the CR.

Basis for meeting the KA res_knowledge of plant procedures for using drawings for configuration change evolutions.

Basis for Hi Cog Basis for SRO only From the Clarification Guidance for SRO-only Questions dacument:

This question meets the following:

Knowledge of administrative procniures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures Requires familiarity with proper procedures for configuration change evolutions.

Only an SRO performs this task.

Job Level Cognitive Level QuestionType Question Source SRO Memoiy BANK ONS NRC 2007 Q97 Development References Student References Provided OMP 1-2, Rules of Practice GEN2.2 2.2.15 GENERIC Equipment Control Equipment Control Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.10/43.3 /45.13) 401-S Comments: RemarkslStatus Wednesday, April 11, 2012 Page 192 of 202

FOR REVIEW ONLY DO NOT DiSTRIBUTE ILT41 ONS SRO NRC Examination QUESTION 96 96 GEN2.2 2.2.40 GENERIC Equipment Control Equipment Control Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 / 45.3)

Given the following Unit I conditions:

RCS Loops dropped

IALPI pump operating

SR 3.4.8.1 is performed at 2100 on 12-1 Which ONE of the following states the LATEST time that SR 3.4.8.1 can be performed and the specified Frequency of the surveillance still be met?

REFERENCE PROVIDED A. 0900 on 12-2.

B. 1200on12-2.

C. 2100on12-2.

D. 0000 on 12-3.

Wednesday, April 11, 2012 Page 193 of 202

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ILT41 ONS SRO NRC Examination QUESTION 96 L 96 General Discussion Answer A Discussion Incorrect: SR 3.0.2 allows for 25% extension of the interval specified as the frequency. This answer would be correct without the 25% extension applied since SR 3.4.8.1 has a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months frequency.

Answer B Discussion Correct: SR 3.0.2 allows for 25% extension of the interval specified as the frequency. SR 3.4.8.1 has a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months frequency therefore applying the 25% extension results in 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months which is 1200 on 12-2.

Answer C Discussion Incorrect: This would be correct if the surveillance was a SLC requirement and not a TS requirement. SLC 16.2.7 says that SLC frequencies get a 50% extension which would be 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months which is 2100 on 12-2.

Answer D Discussion Incorrect. This would be when to declare the LCO not met if the SR had been discovered not performed at 2100 on 12-1.

Basis for meeting the KA K/A MATCH ANALYSIS Requires knowledge of LPI Tech Specs as pertains to the DFIR mode of operation Basis for Hi Cog Basis for SRO only In accordance with Rev I guidance of Clarification Guidance for SRO-only Questions, this question requires application of generic LCO requirements (specifically SR 3.0.2). The question cannot be answered based on knowing 1 hr or less TS, above the line information, or Tech Spec Safety Limit information.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ONS 2009 SRO Q#87 Development References Student References Provided TS 3.4.8, TS TS 3.4.8 SR 3.0.3 ONS 2009 SRO Q#87 GEN2.2 2.2.40 GENERIC Equipment Control Equipment Control Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 / 45.3) 401-S Comments: Remarks/Status Wednesday, April 11, 2012 Page 194 of 202

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ILT41 ONS SRO NRC Examination QUESTION 97 GEN2.3 2.3.14 GENERIC Radiation Control Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 /

43.4 /45.10)

Given the following Unit I conditions:

Initial conditions:

EOP Enclosure 5.12 (ECCS Suction Swap to RBES) in progress Current conditions:

The step to open 1 HP-939 and I HP-940 has just been completed

1) These valves direct HPI flow to the (1)

2) In accordance with the bases of SLC 16.6.12 (Additional HPI Requirements) this flow path is established to prevent (2)

Which ONE of the following completes the statements above?

A. 1. RBES

2. elevated dose rates in the Auxiliary Building B. 1. RBES

2. Boron precipitation in the core C. 1. LDST

2. elevated dose rates in the Auxiliary Building D. 1. LDST

2. over-pressurization of the letdown line Wednesday, April 11, 2012 Page 195 of 202

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ILT41 ONS SRO NRC Examination QUESTION 97 97 Genera! Discussion Answer A Discussion Correct. 1HP-939/940 provide a flow path from the LDST outlet to the RBES. These valves are opened to prevent the HPI pump recilt flow during piggyback from causing HPI relief valves from opening. If opened this would cause high dose rates in the AB.

Answer B Discussion Incorrect. First part is correct. Second part is plausible a flow path to the RBES is aligned to provide for post LOCA Boron Dilution. However this is not the correct flow path.

Answer C Discussion Incorrect. Plausible if the candidate has the misconception that the valves are used to ensure an HPI pump recirc flow path back to the LDST.

Second part is correct.

Answer D Discussion Incorrect. Plausible if the candidate has the misconception that the valves are used to ensure an HPI pump recir flow path back to the LDST.

Second part is plausible because they do route letdown flow to the RBES which would relive letdown pressure however they are on the outlet of the LDST.

Basis for meeting the KA Question requires knowledge of radation hazards that can occur during a SBLOCA and how it is prevented.

Basis for Hi Cog Basis for SRO only This question requires knowledge from the basis of SLC 16.6.12 that is not systems knowledge.

It cannot be answered by knowing 1 hr or less TS/TRM Action It cannot be answered solely with above the line information.

It cannot be answered solely by knowing Safety Limits Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided PNS-HPI SLC 16.6.12 ADM-TSS EOP End. 5.12 GEN2.3 2.3.14 GENERIC Radiation Control Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 /

43.4/45.10) 401-9 Comments: Remarks/Status Wednesday, April 11,2012 Page 196 of 202

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ILT41 ONS SRO NRC Examination QUESTION 98 GEN2.3 2.3.4 GENERIC Radiation Control Radiation Control Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10)

Given the following Unit I conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

RCS pressure = 1136 psig slowly decreasing

CoreSCM=0°F

RB pressure = 11.6 psig slowly decreasing

IASG pressure= 1010 psig slowly decreasing

I B SG pressure = 1008 psig slowly decreasing

1) Emergency Dose Limits (1) in affect.

2) The maximum (TEDE) dose that an NEO can receive while performing a task outside of the control room without exceeding any applicable limits is (2)

Which ONE of the following completes the statements above?

A. 1. are

2. 5 rem for performing Time Critical Tasks B. 1. are

2. 25 rem for protecting property C. 1. are NOT

2. 2 rem for performing Time Critical Tasks D. 1. are NOT

2. 25 rem for lifesaving activities Wednesday, April 11,2012 Page 197 of 202

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ILT41 ONS SRO NRC Examination QUESTION 98 98 General Discussion Answer A Discussion CORRECT: Plant conditions indicate a LOCA is occurring. This requires EDLs to be in effect. 5 rem is the maximum dose that could be received under EDLs for performing Time Critical Tasks.

Answer B Discussion Incorrect: First part is correct. Second part is incorrect. Plausible because 25 rem is the limit for lifesaving activities.

Answer C Discussion Incorrect: First part is incorrect. Plausible if they miss diagnose a MSLB. Second part is incorrect. Plausible in that 2 rem is the normal administrative limit.

Answer D Discussion Incorrect: First part is incorrect. Plausible if they miss diagnose a MSLB. Second part is incorrect. Plausible because 10 rem is the maximum allowed dose for protecting property. 25 rem is the limit for lifesaving activities.

Basis for meeting the KA Requires knowledge of whether emergency dose limits are in effect and for what task they apply Basis for Hi Cog Basis for SRO only The SRO as the procedure director evaluates facility conditions and determines if EDLs are in affect.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ONS 2009 Q#99 Development References ent References Provided EOP LOSCM tab I ONS 2009 Q#99 GEN2.3 2.3.4 GENERIC Radiation Control Radiation Control Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10)

[4o19 Comments: Remarks/Status Wednesday, April 11,2012 Page 198 of 202

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ILT41 ONS SRO NRC Examination QUESTION 99 99 GEN2.4 2.4.18 GENERIC Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of the specific bases for EOPs. (CFR: 41.10 I 43.1 / 45.13)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power 100%

Current conditions:

Turbine Building Flood (TB F) tab in progress

1) In accordance with the TBF tab, (1) is the preferred method to maintain stable shutdown conditions.

2) The above method is chosen because (2)

Which ONE of the following completes the statements above?

A. 1. feeding the SGs with SSF ASW

2. BWST inventory is NOT adequate to cool down to LPI B. 1. feeding the SGs with SSF ASW

2. of the expected unavailability of LPSW to cool the RBES C. 1. initiation of HPI forced cooling

2. BWST inventory is adequate to cool down to LPI D. 1. initiation of HPI forced cooling

2. of the negative consequences of putting lake water in the SGs Wednesday, April 11,2012 Page 199 of 202

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ILT41 ONS SRO NRC Examination QUESTION 99 99j General Discussion Answer A Discussion Incorrect. First part is correct. Second part is plausible because the candidate may have the misconception that BWST does not have adequate inventory to cooldown to LPI.

Answer B Discussion Correct. For a TBF, feeding SGs with raw water from SSF ASW or Station ASW is preferred over HPI forced cooling. HPI F/C is not preferred since once the BWST is depleted, water in the RBES is not expected to be available due to unavailability of LPSW for cooling.

Answer C Discussion Incorrect. First part is plausible because HPI F/C is normally preferred over using SSF ASW. Second part is plausible because the candidate may have the misconception that the BWST does not have adequate inventory to cooldown to LPI.

Answer D Discussion ncorrect First part is plausible because HPI F/C is normally preferred over using SSF ASW. Second part is plausible because feeding raw lake water into the SGs is bad but is not the reason in this case.

Basis for meeting the KA Question requires knowledge of the bases for actions taken in the EOP.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions:

Requires assessing plant conditions and determining a section of the procedure with which to proceed. It cannot be answered based solely on systems knowledge or entry conditions, Plant data must be assessed and then the correct section of the procedure applied (feeding SGs with SSF ASW).

Also requires knowledge of the bases for this action.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EAP-TBF R5 TBF tab GEN2.4 2.4.18 GENERIC Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 / 45.13) 401-9 Comments: Remarks/Status Wednesday, April 11,2012 Page 200 of 202

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ILT41 ONS SRO NRC Examination QUESTION 100 ioo GEN2.4 2.4.44 GENERIC Emergency Procedures I Plan Emergency Procedures I Plan Knowledge of emergency plan protective action recommendations. (CFR: 41 .10 I 41 12 / 43.5 145.11)

Given the following Unit I conditions:

Initial conditions:

Time = 0400

The Emergency Plan has been entered due to LBLOCA Current conditions:

Time=0455

The TSC is activated and turnover is complete I) The LOWEST classification which always requires a protective action recommendation on the initial notification is a (I)

2) After 0455, the (2) will notify the State and Counties of additional protective action recommendations.

Which ONE of the following completes the statements above?

A. 1. Site Area Emergency

2. TSC B. I. Site Area Emergency

2. Control Room C. 1. General Emergency

2. TSC D. I. General Emergency

2. Control Room Wednesday, Apr11 11, 2012 Page 201 of 202

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ILT41 ONS SRO NRC Examination QUESTION 100 ioo General Discussion Answer A Discussion Incorrect. First part is plausible because PARs are for the initial notification with a Conditons A or B for one of the dams or dikes. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because PARs are for the initial notification with a Conditions A or B for one of the dams or dikes. Second part is plausible because the Control Room handles off-site communications until the TSC is activated..

Answer C Discussion Correct. The General Emergency is the only classification that requires PARs any time it is used. The TSC handles off-site communications after it is activated.

Answer D Discussion Incorrect. First part is correct. Second part is plausible because the Control Room handles off-site communications until the TSC is activated...

Basis for meeting the KA The question requires knowledge of PARs, which is a function of the emergency coordinator.

Basis for Hi Cog Basis for SRO only OSM will be the initial emergency coordinator during the event. It could be his responsibility to make the initial PAR. An RO would not be required to know this.

Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided EAP-SEP ROt LPer_RPIO/B/l 000/002, GEN2.4 2.4.44 GENERIC Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of emergency plan protective action recommendations. (CFR: 41.10 / 41.12 / 43.5 / 45.11) 401-9 Comments: Remarks/Status Wednesday, April 11,2012 Page 202 of 202

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Reference Listfor: ILT41 ONS SRO NRC Examinati Question Reference List Number 16 AP/34 Capability curve 61 AP/35 End. 5.4 73 Plan View RWP 23 80 TS 3.8.8 86 RP/0/BI1000I001 Encl.4.1 -4.9 89 RPIOIBII000IOOI End. 4.1 -4.9 91 TS 3.5.2 93 SLC16.11.3 96 TS3.4.8 Printed 4/I 1/2012 12:41:09 PM Page 1 of I

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